In this paper,we have addressed the problem of the radiation transport with the Monte Carlo N-particle(MCNP) code.This is a general-purpose Monte Carlo tool designed to transport neutron,photon and electron in three d...In this paper,we have addressed the problem of the radiation transport with the Monte Carlo N-particle(MCNP) code.This is a general-purpose Monte Carlo tool designed to transport neutron,photon and electron in three dimensional geometries.To examine the performance of MCNP5 code in the field of external radiotherapy,we performed the modeling of an Electron Density phantom(EDP) irradiated by photons from 60Co source.The model was used to calculate the Percent Depth Dose(PDD) at different depths in an EDP.One field size for PDD has been examined.A 60Co photons source placed at 80 cm source to surface distance(SSD).The results of calculations were compared to TPS data obtained at National Institute of Oncology of Rabat.展开更多
基金Laboratory of Radiation and Nuclear Systems (LRSN)
文摘In this paper,we have addressed the problem of the radiation transport with the Monte Carlo N-particle(MCNP) code.This is a general-purpose Monte Carlo tool designed to transport neutron,photon and electron in three dimensional geometries.To examine the performance of MCNP5 code in the field of external radiotherapy,we performed the modeling of an Electron Density phantom(EDP) irradiated by photons from 60Co source.The model was used to calculate the Percent Depth Dose(PDD) at different depths in an EDP.One field size for PDD has been examined.A 60Co photons source placed at 80 cm source to surface distance(SSD).The results of calculations were compared to TPS data obtained at National Institute of Oncology of Rabat.
